L-17-158, Reply to Request for Additional Information Re License Renewal Commitment No. 42

Reply to Request for Additional Information Re License Renewal Commitment No. 42

ML17136A362
Person / Time
Site:	Davis Besse
Issue date:	05/12/2017
From:	Boles B FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-17-158
Download: ML17136A362 (15)

Text

FENOC' 5501 North State Route 2 Oak Harbor. Ohio 43449 RrstEnergy Nuclear Operating Company Brian D. Boles 419-321-7676 Vice President. Nuclear May 12, 2017 L-17-158 ATTN : Document Control Desk U.S . Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346 , License Number NPF-3 Reply to Request for Additional Information Related to License Renewal Commitment No. 42 By letter dated April 21 , 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16112A079), FirstEnergy Nuclear Operating Company (FENOC) submitted a Fatigue Monitoring Program evaluation for Davis-Besse Nuclear Power Station , Unit No. 1 (DBNPS), to address License Renewal Commitment 42. By letter dated September 26, 2016 (ADAMS Accession No.

ML16270A447), FENOC submitted a reply to a U.S. Nuclear Regulatory Commission (NRG) request for additional information regarding FENOC's April 21, 2016 letter.

By letter dated January 23 , 2017 (ADAMS Accession No. ML16364A279), the NRG requested additional information to complete its review of FENOC's Fatigue Monitoring Program evaluation. By letter dated February 22, 2017 (ADAMS Accession No.

ML17054D480) , FENOC provided a reply to the NRG request for additional information ,

and committed to the following actions by April 28 , 2017:

FENOC will evaluate the limiting nickel-based alloy (NBA) and low-alloy steel (LAS) components for environmentally-assisted fatigue (EAF) for 60-year projected cycles. In addition, Davis-Besse plans to evaluate the remaining locations with EAF greater than 1. 0 that were considered bounded by other locations. These locations were identified in FENOC Letter dated September 26, 2016 (ADAMS Accession No. ML16270A447),

Table 1. FENOC will submit the results of the evaluations to the Nuclear Regulatory Commission.

These evaluations took longer than expected and were not complete in time to meet the April 28, 2017, due date. On April 27, 2017, FENOC contacted the DBNPS NRC Project Manager by telephone to discuss a new due date, and both parties agreed to a May 12, 2017 , submittal date. fi/4-5 fi)~?

Davis-Besse Nuclear Power Station, Unit No. 1 L-17-158 Page 2 FENOC has completed fatigue evaluations for the additional plant-specific component materials and locations as described in the commitment. The Attachment provides the results of the evaluations .

If there are any questions or if additional information is required , please contact Mr. Patrick McCloskey, Manager- Regulatory Compliance, at (419) 321-7274.

Sincerely, Brian D. Boles

Attachment:

Reply to Request for Additional Information Related to Davis-Besse Nuclear Power Station , Unit No. 1 (DBNPS), License Renewal Commitment 42 cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board

Attachment L-17-158 Reply to Request for Additional Information (RAI) Related to Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS) ,

License Renewal Commitment 42 Page 1 of 12 By letter dated January 23 , 2017 (ADAMS Accession No. ML16364A279), the NRC requested additional information to complete its review of FENOC's Fatigue Monitoring Program evaluation . By letter dated February 22 , 2017 (ADAMS Accession No.

ML17054D480), FENOC provided a reply to the NRC request for additional information ,

and committed to the following actions:

FENOC will evaluate the limiting nickel-based alloy (NBA) and low-alloy steel (LAS) components for environmentally-assisted fatigue (EAF) for 60-year projected cycles. In addition, Davis-Besse plans to evaluate the remaining locations with EAF greater than 1.0 that were considered bounded by other locations. These locations were identified in FENOC Letterdated September 26, 2016 (ADAMS Accession No. ML16270A447),

Table 1. FENOC will submit the results of the evaluations to the Nuclear Regulatory Commission.

FENOC has completed evaluation of environmentally-assisted fatigue (EAF) for all Davis-Besse Reactor Coolant System (RCS) pressure boundary locations that are in contact with the RCS environment. See Table 1 for a complete list of the components being managed for EAF by the Fatigue Monitoring Program . Differences from Table 1 provided in FENOC letter dated February 22 , 2017 , are highlighted in Table 1, below.

As described in FENOC letter dated September 26, 2016, a location was eliminated if it met one of the following prescreening criteria :

• The location has a usage factor that is so low that, even if the maximum possible environmental fatigue correction factor (Fen) were applied , the resulting EAF cumulative usage factor (CUFen) would be less than 0.8 , which is the example EAF screening limit provided in EPRI Technical Report 1024995, "Environmentally Assisted Fatigue Screening: Process and Technical Basis for Identifying EAF Limiting Locations."

• The location is not exposed to reactor water, and therefore EAF is not applicable.

• The location is not part of the primary pressure boundary and is therefore excluded from the EPRI screening process .

The locations with an CUFen greater than 1.0 were then evaluated per NUREG/CR-6260, "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, " Section 4.3, "Potential Adjustments to Licensees'

Attachment L-17-158 Page 2 of 13 Calculations that Might Reduce the CUF ," to determine sources of conservatism in the existing fatigue usage calculations and reduce the CUFen below 1.0. However, no locations were bounded by another in the final list of components being managed for EAF by the Fatigue Monitoring Program.

Table 2 provides the list of components being managed for EAF by the Fatigue Monitoring Program , sorted by material type and CUFen for identification of the limiting locations for each material.

Attachment L-17-158 Page 3 of 13 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program Material Component Location CUF CUFadj Fen CUFen Notes Type RV Closure, Head LAS 0.03 2.45 0.07 RV Closure, Vessel LAS 0.02 2.45 0.05 CRDM Housing, Adapter SS 0.014 15.35 0.21 CRDM Housing, Body Ni-Cr-Fe 0.08 4.78 0.38 CRDM Housing, Blind Flanges SS 0.0024 15.35 0.04 CRDM Housing, Motor Tube Flanges SS 0.00 15.35 0 Inlet Nozzle LAS 0.829 0.146 2.45 0.358 NUREGICR-6260 Location Outlet Nozzle LAS 0.768 0.335 2.45 0.821 NUREGICR-6260 Location Reactor Vessel Core Flood Nozzle to Safe End SS 0.064 15.34 0.982 Core Flood Nozzle LAS 0.0504 2.45 0.123 NUREGICR-6260 Location Incore Instrument Nozzles Ni-Cr-Fe 0.770 0.206 4.16 0.857 NUREGICR-6260 Location Segmented Skirt, Head to Skirt Structure cs 0.254 1.74 0.44 RV Shell, Nozzle Belt LAS 0.024 2.45 0.059 RV Shell, Lower Head LAS 0.024 2.45 0.059 NUREGICR-6260 Location Continuous Vent Nozzle, Reducer to Pipe Weld SS 0.001 15.35 0.02 Continuous Vent Nozzle, J-Groove Weld Ni-Cr-Fe 0.9 0.0719 4.52 0.325 Reactor Coolant RC pump cover, cooling hole ligament SS 0.56 NIA NIA See Note 1 Pumps RC pump cover, bearing cavity SS 0.964 0.032 15.35 0.49

Attachment L-17-158 Page 4 of 13 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

Material Component Location CUF CUFadj Fen CUFen Notes Type Spray Nozzle, Nozzle cs 0.01 1.74 0.02 Spray Nozzle, Safe End Ni-Cr-Fe 0.01 4.78 0.05 Spray Nozzle, Nozzle I Head Juncture cs 0.01 1.74 0.02 Spray Nozzle, Weld Overlay Ni-Cr-Fe 0.01 4.78 0.05 Surge Nozzle, Inside Radius cs 0.182 1.74 0.317 NUREG/CR-6260 Location Surge Nozzle, Safe End SS 0.108 0.0581 15.35 0.892 NUREG/CR-6260 Location Surge Nozzle, Piping to Safe End Weld SS 0.619 1.49 0.922 NUREG/CR-6260 Location Vessel Support Lugs, Support cs 0.01 1.74 0.02 Vessel Support Lugs, Shell cs 0.01 1.74 0.02 Heater Bundle Closure, Cover Plate LAS 0.05 2.45 0.123 Heater Bundle Closure, Diaphragm Plate SS 0.41 *

• 0.92 *See Note 3 Heater Bundle Closure, Seal Weld SS 0.66 *

• 0.75 *See Note 3 Pressurizer Shell, Heater Belt Transition cs 0.13 1.74 0.23 3" Pressurizer Relief Nozzle, Nozzle cs Exempt See Note 4 3" Pressurizer Relief Nozzle, Safe End SS Exempt See Note 4 3" Pressurizer Relief Nozzle, Upper Head cs Exempt See Note 4 Other Openings, Vent Nozzle Ni-Cr-Fe Exempt See Note 5 Other Openings, Level Sensing Nozzle (Upper) Ni-Cr-Fe Exempt See Note 5 Other Openings, Level Sensing Nozzle (Lower) Ni-Cr-Fe Exempt See Note 5 Other Openings, Level Sensing Nozzle (Lower)

Ni-Cr-Fe 0.166 4.78 0.793 Opening Other Openings, Thermowell Nozzle Ni-Cr-Fe Exempt See Note 5 Other Openings, Thermowell Nozzle Opening Ni-Cr-Fe 0.166 4.78 0.793 Other Openings, Sampling Nozzle Ni-Cr-Fe Exempt See Note 5 Other Openings, Sampling Nozzle Opening Ni-Cr-Fe 0.166 4.78 0.793 Other Openings, Manway cs Exempt See Note 5

Attachment L-17-158 Page 5 of 13 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

Material Component Location CUF CUFadj Fen CUFen Notes Type Primary Manways LAS 0.34 2.45 0.83 Primary Manway Diaphragm Seal Welds See Note 6 Primary Handhole Cover LAS 0.37 2.45 0.91 Primary Handhole Diaphragm Seal Weld See Note 6 In let Nozzle I Primary Head Juncture LAS 0.79 0.0351 2.45 0.09 Primary Outlet Nozzles LAS 0.14 2.45 0.34 Outlet Nozzle I Primary Head Junctures LAS 0.25 2.45 0.61 Lower Primary Head away from Outlet Nozzles LAS 0.11 2.45 0.27 Steam Upper Primary Head I Tubesheet Knuckle Generators incl uding Vent I Level Sensing and Acoustic LAS 0.28 2.45 0.69 (See Note 7) Sensor Lower Primary Head I Tubesheet Knuckle LAS 0.08 2.45 0.20 Perforated Tubesheets, Postulated Thin LAS 0.39 2.45 0.96 Ligament (Primary Side)

Lower Spherical I Flat Head Juncture LAS 0.33 2.45 0.81 Lower Flat Head LAS 0.10 2.45 0.25 Tubes Ni-Cr-Fe 0.36 0.1747 2.074 0.362 See Note IO Tube Seal Welds Ni-Cr-Fe 0.42 0.1693 4.327 0.732 See Note 10 Tube P lug Seal Welds Ni-Cr-Fe 0.23 0.1256 3.796 0.477 See Note 10

Attachment L-17-158 Page 6 of 13 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

Material Component Location CUF CUFadj Fen CUFen Notes Type Hot Leg Piping cs 0.827 0.184 1.74 0.320 Upper Cold Leg Piping cs 0.059 1.74 0.10 Lower Cold Leg cs 0.183 1.74 0.32 Pressurizer Surge Line, Hot Leg Surge Nozzle Inside Radius cs 0.445 1.74 0.774 NUREG/CR-6260 Location Pressurizer Surge Line, Piping Adjacent to Reactor Coolant Outboard End of Hot Leg Surge Nozzle (End of SS 0.179 0.0385 9.05 0.348 NUREG/CR-6260 Location System (RCS) Hot Leg Weld Overlay)

Piping Pressurizer Surge Line, Piping Elbows SS 0.6463 0.0833 11.13 0.927 NUREG/CR-6260 Location Pressurizer Surge Line, Pi ping Straights SS 0.7658 0.0953 9.85 0.939 NUREG/CR-6260 Location Reactor Coolant Pump Discharge Nozzle SS 0.0007 15.35 0.01 Reactor Coolant Pump Suction Nozzle SS 0.0004 15.35 0.01 Spray Line Piping (Auxiliary Spray) SS 0.486 0.055 15.35 0.844 Spray Line Piping (Main Spray) SS 0.454 *

• 0.743 *See Note 8 Decay Heat Nozzle cs 0.89 0.5269 1.74 0.92

Attachment L-17-158 Page 7 of 13 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

Material Component Location CUF CUFadj Fen CUFen Notes Type HPI/MU Nozzle cs 0.226 0.271 1.74 0.472 NUREG/CR-6260 Location NUREG/CR-6260 Location SS 0.141 0.064

• 0.434 HPI/MU Nozzle, Safe End including Weld *See Note 8 Letdown Piping SS 0.604 0.04774 15.35 0.73 RC Drain Nozzles SS 0.132 0.1184

• 0.8866 *See Note 9 HPI Lines SS 0.9115 0.008 15.35 0.123 HPI Lines, Elbowlet SS 0.981 0.045 15.35 0.691 Reactor Coolant System (RCS) Core Flood Piping SS 0.582 0.23967 2.55 0.61 Piping Continuous Vent Line SS 0.0318 15.35 0.49 Core Flood Tank Discharge Check Valves SS 0.02839 15.35 0.44 Decay Heat Containment Isolation Valves SS 0.14594 0.01268 15.35 0.19 Decay Heat Bypass Containment Isolation SS 0.02732 15.35 0.42 Valves Low Pressure Injection Check Valves SS 0.14099 0.00935 15.35 0.14 Low Pressure Injection Containment Isolation SS 0.18261 0.01294 15.35 0.20 Valves Decay Heat Decay Heat Class 1 Piping SS 0.23303 2.55 0.595 NUREG/CR-6260 Location Piping

Attachment L-17-158 Page 8 of 13 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

NOTES (1) Location not exposed to RCS environment, therefore not subject to EAF.

(2) Not a RCS Pressure Boundary Component.

(3) Detailed elastic and elastic-plastic analyses completed to determine adjusted usage factors. For the elastic portion of the fatigue usage, the maximum Fen factor of 15.35 is conservatively applied. For the elastic-plastic portion, a detailed Fen calculation is performed.

(4) These nozzles are shown acceptable by satisfying requirements of paragraphs N-415.1 and N-450 of ASME Section III - 1968 Edition with Summer 1968 Addenda.

(5) These nozzles are shown acceptable by satisfying the requirements of paragraph N-415.1 of ASME Section III- 1968 Edition with Summer 1968 Addenda (6) Covers are sealed using gaskets and seal welds were not used, therefore fatigue calculations not required.

(7) Only primarv RCS Pressure Boundarv locations with CUF greater than 0.052 are evaluted for EAF.

(8) EAF CUF determined using integrated strain rate Fen factors.

(9) CUFen determined using NUREG/CR-6909 rules. The strain amplitude is less than the strain amplitude threshold of 0.10% in all cases, Fen does not need to be applied.

(10) EAF CUF determined using integrated strain rate Fen factors. Average adjusted CUF and Fen factors listed.

Attachment L-17-158 Page 9 of 13 Table 2: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program (sorted by material type and EAF cumulative usage factor)

Material Component Location CUF CUFadj Fen CUFen Notes Type RCS Piping Decay Heat Nozzle cs 0.89 0.5269 1.74 0.92 Pressurizer Surge Line, Hot Leg Surge Nozzle Inside RCS Piping Radius cs 0.445 1.74 0.774 NUREG/CR-6260 Location RCS Piping HPl/MU Nozzle cs 0.226 0.271 1.74 0.472 NUREG/CR-6260 Location Reactor Vessel Segmented Skirt, Head to Skirt Structure cs 0.254 1.74 0.44 RCS Piping Hot Leg Piping cs 0.827 0.184 1.74 0.320 RCS Piping Lower Cold Leg cs 0.183 1.74 0.32 Pressurizer Surge Nozzle, Inside Radius cs 0.182 1.74 0.317 NUREG/CR-6260 Location Pressurizer Shell, Heater Belt Transition cs 0.13 1.74 0.23 RCS Piping Upper Cold Leg Piping cs 0.059 1.74 0.10 Pressurizer Spray Nozzle, Nozzle cs 0.01 l.74 0.02 Pressurizer Spray Nozzle, Nozzle I Head Juncture cs 0.01 l.74 0.02 Pressurizer Vessel Support Lugs, Support cs 0.01 1.74 0.02 Pressurizer Vessel Support Lugs, Shell cs 0.01 1.74 0.02 Pressurizer 3" Pressurizer Relief Nozzle, Nozzle cs Exempt Pressurizer 3" Pressurizer Relief Nozzle, Upper Head cs Exempt Pressurizer Other Openings, Manway cs Exempt

Attachment L-17-158 Page 10of13 Table 2: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

(sorted by material type and EAF cumulative usage factor)

Material Component Location CUF CUFadj Fen CUFen Notes Type Perforated Tubesheets, Postulated Thin Ligament Steam Generators LAS 0.39 2.45 0.96 (Primary Side)

Steam Generators Primary Handhole Cover LAS 0.37 2.45 0.91 Steam Generators Primary Manways LAS 0.34 2.45 0.83 Reactor Vessel Outlet Nozzle LAS 0.768 0.335 2.45 0.821 NUREG/CR-6260 Location Steam Generators Lower Spherical I Flat Head Juncture LAS 0.33 2.45 0.81 Upper Primary Head I Tubesheet Knuckle including Steam Generators LAS 0.28 2.45 0.69 Vent I Level Sensing and Acoustic Sensor Steam Generators Outlet Nozzle I Primary Head Junctures LAS 0.25 2.45 0.61 Reactor Vessel Inlet Nozzle LAS 0.829 0.146 2.45 0.358 NUREG/CR-6260 Location Steam Generators Primary Outlet Nozzles LAS 0.14 2.45 0.34 Steam Generators Lower Primary Head away from Outlet Nozzles LAS 0.11 2.45 0.27 Steam Generators Lower Flat Head LAS 0.10 2.45 0.25 Steam Generators Lower Primary Head I Tubesheet Knuckle LAS 0.08 2.45 0.20 Reactor Vessel Core Flood Nozzle LAS 0.0504 2.45 0.123 NUREG/CR-6260 Location Pressurizer Heater Bundle Closure, Cover Plate LAS 0.05 2.45 0.123 Steam Generators Inlet Nozzle I Primary Head Juncture LAS 0.79 0.0351 2.45 0.09 Reactor Vessel RV Closure, Head LAS 0.03 2.45 0.07 Reactor Vessel RV Shell, Nozzle Belt LAS 0.024 2.45 0.059 Reactor Vessel RV Shell, Lower Head LAS 0.024 2.45 0.059 NUREG/CR-6260 Location Reactor Vessel RV Closure, Vessel LAS 0.02 2.45 0.05

Attachment L-17-158 Page 11 of 13 Table 2: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

(sorted by material type and EAF cumulative usage factor)

Material Component Location CUF CUFadj Fen CUFen Notes Type Reactor Vessel Incore Instrument Nozzles Ni-Cr-Fe 0.770 0.206 4.16 0.857 NUREG/CR-6260 Location Other Openings, Level Sensing Nozzle (Lower)

Pressurizer Ni-Cr-Fe 0.166 4.78 0.793 Opening Pressurizer Other Openings, Thermowell Nozzle Opening Ni-Cr-Fe 0.166 4.78 0.793 Pressurizer Other Openings, Sampling Nozzle Opening Ni-Cr-Fe 0.166 4.78 0.793 Steam Generators Tube Seal Welds Ni-Cr-Fe 0.42 0.1 693 4.327 0.732 Steam Generators Tube Plug Seal Welds Ni-Cr-Fe 0.23 0.1256 3.796 0.477 Reactor Vessel CRDM Housing, Body Ni-Cr-Fe 0.08 4.78 0.38 Steam Generators Tubes Ni-Cr-Fe 0.36 0.1747 2.074 0.362 Reactor Vessel Continuous Vent Nozzle, J-Groove Weld Ni-Cr-Fe 0.9 0.0719 4.52 0.325 Pressurizer Spray Nozzle, Safe End Ni-Cr-Fe 0.01 4.78 0.05 Pressurizer Spray Nozzle, Weld Overlay Ni-Cr-Fe 0.01 4.78 0.05 Pressurizer Other Openings, Vent Nozzle Ni-Cr-Fe Exempt Pressurizer Other Openings, Level Sensing Nozzle (Upper) Ni-Cr-Fe Exempt Pressurizer Other Openings, Level Sensing Nozzle (Lower) Ni-Cr-Fe Exempt Pressurizer Other Openings, Thermowell Nozzle Ni-Cr-Fe Exempt Pressurizer Other Openings, Sampling Nozzle Ni-Cr-Fe Exempt

Attachment L-17-158 Page 12of13 Table 2: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

(sorted by material type and EAF cumulative usage factor)

Material Component Location CUF CUFadj Fen CUFen Notes Type Reactor Vessel Core Flood Nozzle to Safe End SS 0.064 15.34 0.982 RCS Piping Pressurizer Surge Line, Piping Straights SS 0.7658 0.0953 9.85 0.939 NUREG/CR-6260 Location RCS Piping Pressurizer Surge Line, Piping Elbows SS 0.6463 0.0833 11.13 0.927 NUREG/CR-6260 Location Pressurizer Surge Nozzle, Piping to Safe End Weld SS 0.619 1.49 0.922 NUREG/CR-6260 Location Pressurizer Heater Bundle Closure, Diaphragm Plate SS 0.41 *

• 0.92 Pressurizer Surge Nozzle, Safe End SS 0.108 0.0581 15.35 0.892 NUREG/CR-6260 Location RCS Piping RC Drain Nozzles SS 0.132 0.1184

• 0.8866 RCS Piping Spray Line Piping (Auxiliary Spray) SS 0.486 0.055 15.35 0.844 Pressurizer Heater Bundle Closure, Seal Weld SS 0.66 *

• 0.75 RCS Piping Spray Line Piping (Main Spray) SS 0.454 *

• 0.743 RCS Piping Letdown Piping SS 0.604 0.04774 15.35 0.73 RCS Piping HPI Lines, Elbowlet SS 0.981 0.045 15.35 0.691 RCS Piping Core Flood Piping SS 0.582 0.23967 2.55 0.61 Decay Heat Decay Heat Class 1 Piping SS 0.23303 2.55 0.595 NUREG/CR-6260 Location Piping

[Stainless Steel (SS) material continued on next page]

Attachment L-17-158 Page 13of13 Table 2: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.

(sorted by material type and EAF cumulative usage factor)

Material Component Location CUF CUFadj Fen CUFen Notes Type Reactor Coolant RC pump cover, bearing cavity SS 0.964 0.032 15.35 0.49 Pumps RCS Piping Continuous Vent Line SS 0.0318 15.35 0.49 RCS Piping Core Flood Tank Discharge Check Valves SS 0.02839 15.35 0.44 RCS Piping HPI/MU Nozzle, Safe End including Weld SS 0.141 0.064

• 0.434 NUREG/CR-6260 Location RCS Piping Decay Heat Bypass Containment Isolation Valves SS 0.02732 15.35 0.42 Pressurizer Surge Line, Piping Adjacent to Outboard RCS Piping End of Hot Leg Surge Nozzle (End of Hot Leg SS 0.179 0.0385 9.05 0.348 NUREG/CR-6260 Location Weld Overlay)

Reactor Vessel CRDM Housing, Adapter SS 0.014 15.35 0.21 Low Pressure Injection Containment Isolation RCS Piping SS 0.18261 0.01294 15.35 0.20 Valves RCS Piping Decay Heat Containment Isolation Valves SS 0.14594 0.01268 15.35 0.19 RCS Piping Low Pressure Injection Check Valves SS 0.14099 0.00935 15.35 0.14 RCS Piping HPI Lines SS 0.9115 0.008 15.35 0.123 Reactor Vessel CRDM Housing, Blind Flanges SS 0.0024 15 .35 0.04 Reactor Vessel Continuous Vent Nozzle, Reducer to Pipe Weld SS 0.001 15.35 0.02 RCS Piping Reactor Coolant Pump Discharge Nozzle SS 0.0007 15.35 0.01 RCS Piping Reactor Coolant Pump Suction Nozzle SS 0.0004 15.35 0.01 Reactor Vessel CRDM Housing, Motor Tube Flanges SS 0.00 15 .35 0 Pressurizer 3" Pressurizer Relief Nozzle, Safe End SS Exempt